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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20117L7271996-09-0505 September 1996 Proposed Tech Specs 4.2-2 Re Steam Generator non-repaired Tube Insp & 4.2-3 Re Steam Generator Repaired Tube Insp ML20092K8131995-09-19019 September 1995 Proposed Tech Specs,Providing Revs to Clarify Purposes to Maintain Accuracy of TS & Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20091P1041992-01-27027 January 1992 Proposed Tech Specs Re Steam Generator Tube Sleeving ML1116601091981-08-0707 August 1981 Proposed Amend 46 to Tech Specs 3.4,3.10,Table 3.1-2,Figures 3.1-1,3.1-2,3.10-7 & Pages 3.1-2,3.1.2a,3.1.2b,3.1-2,3.1-3, 3.1-6,3.1-7,4.2-2a,4.2-8 & 6-2 for Pressure Safety Isolation Valves & Normal Operation Heatup/Cooldown Limits ML19210C9981979-11-16016 November 1979 Proposed Amend 41 to Tech Specs,Changing Limit for Reactivity Anomalies for Comparison of Measured to Predicted Boron Concentrations to 1% Reactivity ML19256E0081979-10-19019 October 1979 Proposed Tech Spec Amend 40,adding Fire Protection Sys Committed to in Amend 23,deleting Mods Required as License Condition,Adding 5-man Fire Response Requirements & Correcting Inconsistencies 1996-09-05
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20117L7271996-09-0505 September 1996 Proposed Tech Specs 4.2-2 Re Steam Generator non-repaired Tube Insp & 4.2-3 Re Steam Generator Repaired Tube Insp ML20092K8131995-09-19019 September 1995 Proposed Tech Specs,Providing Revs to Clarify Purposes to Maintain Accuracy of TS & Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20091P1041992-01-27027 January 1992 Proposed Tech Specs Re Steam Generator Tube Sleeving ML20205H3401987-01-12012 January 1987 Rev 3 to Reactor Test Program,Kewaunee Nuclear Power Plant ML20125B4491985-05-31031 May 1985 Plant,Cycle II Startup Rept,May 1985 ML20108F4791984-08-20020 August 1984 Suppl to Kewaunee Nuclear Power Plant 1984 Integrated Leak Rate Test Rept ML20092K4191984-06-30030 June 1984 Cycle 10 Startup Rept,June 1984 ML20080B9871984-01-12012 January 1984 Emergency Plan Implementing Procedure EP-TSC-7, Reactor Vessel Head Venting Time Calculation ML20080B9721984-01-12012 January 1984 Rev B to Emergency Plan Implementation Procedure EP-RET-3C, Post-Accident Operation of High Radiation Sample Room ML20083F7161983-10-27027 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-3 Re Unusual Event, EP-AD-4 Re Alert & EP-AD-5 Re Site Emergency ML20078L5791983-09-29029 September 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-3 Re Unusual Event, EP-AD-4 Re Alert & EP-AD-5 Re Site Emergency ML20078F4801983-08-16016 August 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-7 Re Notification of Unusual event,EP-AD-8 Re Notification of Alert & EP-AD-9 Re Notification of Site Emergency ML20077Q0481983-07-26026 July 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-ENV-8 Re Total Population Dose Estimate calculations,EP-RET-5 Re Plume Projection & EP-RET-6 Re Dose Projection ML20077B6001983-07-15015 July 1983 Cycle 9 Startup Rept for June 1983 ML20078G4201983-06-21021 June 1983 Rev D to Procedure EP-ENV-3F Manual Determination of X/Q (Green Bay Meteorological Data) ML20078G4431983-06-21021 June 1983 Rev a to Procedure EP-RET-3D Containment Air Sampling Analysis Using Casp ML20078G4371983-06-21021 June 1983 Rev B to Procedure EP-ENV-3H Protective Action Recommendations ML20078G4331983-06-21021 June 1983 Rev D to Procedure EP-ENV-3G Manual Projection Calculation ML20078G3681983-06-21021 June 1983 Rev H to Procedure EP-ENV-3A Environ Protection Director Actions & Directives ML20078G4061983-06-21021 June 1983 Rev E to Procedure EP-ENV-3E Manual Determination of X/Q (Knpp Meteorological Data) ML20078G3981983-06-21021 June 1983 Procedure EP-ENV-3D Primary Determination of Meteorological Data ML20078G3941983-06-21021 June 1983 Procedure EP-ENV-3C Primary Dose Projection Calculation - Ibm Personal Computer ML20078G3501983-06-21021 June 1983 Rev C to Procedure EP-AD-11 Emergency Radiation Controls ML20077E0041983-06-21021 June 1983 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-11 Re Emergency Radiation Controls & EP-ENV-3A Re Environ Protection Director Actions ML20078G3781983-06-21021 June 1983 Rev E to Procedure EP-ENV-3B EM Team Actions ML20069J5071983-03-10010 March 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-AD-2 Re Emergency Class Determination & EP-AD-11 Re Emergency Radiation Controls ML20069F8351983-03-0101 March 1983 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedure EP-SEC-2, Security Force Response to Emergencies. Revised Table of Contents Encl ML20028D4811983-01-0303 January 1983 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-1, Plant Emergency Organization & EP-OP-3, Control Room Communications. Revised Index Encl ML20066E2691982-10-13013 October 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-2 Re Emergency Class determination,EP-AD-7 Re Notification of Unusual Event & EP-AD-8 Re Notification of Alert ML20062E0801982-07-0202 July 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Revision E to Procedure EP-ENV-3A, Environ Protection Director Actions & Directives. Revised Index Encl ML20058F6741982-06-18018 June 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-17 Re Communications & EP-RET-3C Re post-accident Operation of High Radiation Sample Room ML20054F3961982-05-21021 May 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-ENV-3B Re Environ Monitoring Team Actions & EP-ENV-4A Re Sample Acquisition,Portable Instrument Use ML20052H8421982-04-16016 April 1982 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-7 Re Notification of Unusual Event & EP-AD-8 Re Notification of Alert ML20052B1051982-03-19019 March 1982 Public Version of Revision a to Emergency Plan Implementing Procedures EP-RET-2F, Personnel Decontamination. Revised Index Encl ML20042B2491982-02-18018 February 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure EP-EOF-1 Re Corporate Emergency Response Organization & EP-EOF-2 Re Emergency Operations Facility Activation.Revised Index Encl ML20049H4151982-01-29029 January 1982 Public Version or Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-ENV-5C Sam II Operation & EP-EOF-4 Re Corporate Response to Alert.Revised Index Encl ML20040F9781982-01-15015 January 1982 Public Version of Revised Emergency Plan Implementing Procedures EP-OSF-1 Re Operational Support Facility Emergency Organization & EP-OSF-3 Re Work Requests During Emergency.Revised Table of Contents Encl ML20039H1491981-12-21021 December 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-AD-3 Re Unusual Event & EP-AD-4 Re Notification of Unusual Event ML20038C3821981-10-21021 October 1981 Public Version of Radiological Emergency Response Plan Implementing Procedures,Including Procedures EP-AD-1 Re Plant Emergency organization,EP-AD-2 Re Emergency Classification Determination & EP-AD-3 Re Unusual Event ML1116601091981-08-0707 August 1981 Proposed Amend 46 to Tech Specs 3.4,3.10,Table 3.1-2,Figures 3.1-1,3.1-2,3.10-7 & Pages 3.1-2,3.1.2a,3.1.2b,3.1-2,3.1-3, 3.1-6,3.1-7,4.2-2a,4.2-8 & 6-2 for Pressure Safety Isolation Valves & Normal Operation Heatup/Cooldown Limits ML20038A5641981-07-0101 July 1981 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures ECD 16.1 Re Corporate Emergency Response & ECD 16.2 Re Emergency Operations Facility Activation ML20038A5761981-06-0303 June 1981 Public Version of Revised Radiological Emergency Response Plan Implementing Procedures,Including Procedures ECD 16.1 Re Corporate Emergency Response & Acd 12.1 Re Emergency Organization Structure ML20038A5631981-03-31031 March 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Acd 12.1 Re Emergency Organizational Structure,Acd 12.3 Re Unusual Event Notification & Acd 12.4 Re Alert ML20038A5661981-02-27027 February 1981 Public Version of Radiological Emergency Response Plan Implementing Procedures,Description of Meteorological Monitoring Sys Implementation & Public Info Plan ML19210C9981979-11-16016 November 1979 Proposed Amend 41 to Tech Specs,Changing Limit for Reactivity Anomalies for Comparison of Measured to Predicted Boron Concentrations to 1% Reactivity ML19256E0081979-10-19019 October 1979 Proposed Tech Spec Amend 40,adding Fire Protection Sys Committed to in Amend 23,deleting Mods Required as License Condition,Adding 5-man Fire Response Requirements & Correcting Inconsistencies 1996-09-05
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ATTACHMENT 1 l i
I Letter from C. R. Steinhardt (WPSC) :
To l Document Control Desk (NRC) !
Dated September 5,1996 l
Ploposed Amendment 138b l
Affected TS Pages:
TS v TS 4.2-4 Table TS 4.2-2 Table TS 4.2-3
. n:\ group \ nuclear \wpfiles\lic\nn:\pa l 38b.wpd 9609170114 PDR 960905 ADOCK 05000305 P pgg
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LIST OF TABLES l
l TABLE TITLE l 1.0-1 . . . Frequency Notations 3.1-1 . . . WPS (136) Reactor Vessel Toughness Data 3.1-2 . . . Reactor Coolant System Pressure Isolation Valves i 3.5-1 . . . Engineered Safety Features Initiation Instrument Setting Limits 3.5-2 . . . Instrument Operation Conditions for Reactor Trip 1 3.5-3 . . . Emergency Cooling 3.5-4 . . . Instrument Operating Conditions for Isolation Functions 3.5-5 . . . Instrument Operation Conditions for Safeguards Bus Power l Supply Functions 3.5-6 . . . Accident Monitoring Instrumentation Operating Conditions for l Indication !
4.1-1 . . . Minimum Frequencies for Checks, Calibrations and Test of Instrument Channels 4.1-2 . . . Minimum Frequencies for Sampling Tests 4.1-3 . . . Minimum Frequencies for Equipment Tests 4.2-1 . . . Deleted 4.2-2 . . . Steam Generator Non-Repaired Tube Inspection ,
4:2-311. :A 15 team Generator . Repaired TubelInspection l
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i Proposed Amendment No. 138b i TS v 09/05/96 !
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} e. If a tube does not permit the passage of the eddy current l inspection probe the entire length and through the U-bend, this
, shall be recorded and an adjacent tube shall be inspected. The
- tube which did not allow passage of the eddy current probe .shall '
j be considered degraded.
1 The results of each sample inspection shall be classified into one of the following three categoriesh Tor 7nontrepsifsd[tsties actionitsh'a~11?be taken as described in' Table'4'.222TTorJrepaired j tubes ,j act,i oristis h sl 11beit'aken Latdes c ri. bed 2 i n ; Tabl e% 2s3 E~ ~ ' ~ ,
i j Cateaory Inspection Results >
l 1
C-1 Less than 5% of the total tubes inspected are degraded l 4
tubes, and none of the inspected tubes are defective.
B.
$ C-2 One or more tubes, but not more than 1% of the total tubes inspected are defectite, or between 5% and 10% of
- the total tubes inspected are degraded tubes. ,
1
- C-3 More than 10% of the total tubes inspected are degraded i tubes or more than 1% of the inspected tubes are j defective.
NOTE: In all inspections, previously degraded tubes must exhibit .
significant (>10%) further wall penetrations to be included i in the above percentage calculations. ,
- 3. Inspection Freouencies The above required in-service inspections of steam generator tubes shall be performed at the following frequencies: P
- a. In-service inspections shall be performed at refueling intervals ;
not more than 24 calendar months after the previous inspection. I If two consecutive inspections following service under AVT conditions, not including the pre-service inspection, result in all inspection results falling into the C-1 category; or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
- b. If the results of the in-service inspection of a steam generator conducted in accordance with Table 4.2-2 fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months, The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.2.b.3.a and the interval can be extended to a 40-month period.
i Proposed Amendment No. 138b l TS 4.2-4 09/05/96 i
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TABLE TS 4.2-2 .
STEANGENERATORN0$REPAIREDTUBEINSPECTION ,
IST SANPLE INSPECTION 2ND SANPLE INSPECTION 3RD SANPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G. C-2 Plug or repair C-1 None N/A N/A defective tubes and inspect additional 2S C-2 Plug or repair C-1 None tubes in this S'G~ (2) defective tubes and inspect additional 4S C-2 Plug or repair tubes in this S.G. (2) defective tubes C-3 Perform action for C-3 result of first sample C-3 Perform action for C-3 N/A N/A result of first sample C-3 Inspect all tubes in The other None N/A N/A this S.G., (2) plug or S.G.'s are repair defective tubes C-1 and inspect 2S tubes in the other S.G. (2) Some Perform action for C-2 N/A N/A S.G.'s C-2 result of second Prompt notification of but no sample the Commission. (1) additional S.G. are C-3 Additional Inspect all tubes in N/A N/A S.G. is each S.G. and plug or C-3 repair defective tubes. Prompt notification of the Commission. (1) (2)
S=6%/n Where n is the number of steam generator s inspected during an inspection.
Notes: 1. Refer to Specification 4.2(b)(6)(c)
- 2. As allowed by TS 4.2.b.2.d, the second and third sample inspections during each inservice inspection may be less than the full length of each tube by concentrating the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
PAGE 1 0F 1 Proposed Amendment No. 138b 09/05/96
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e TABLEjTS?4!23 STEANGENERATOREREPAIREDlTUBEl INSPECTION ,
IST SANPLE? INSPECTION 2NDTSANPLEJ: INSPECTION Sainpl6751zs Result AstionfRiduiFed Result Adtion Rsquifed A;niihimum ofL:.20%i bf C!1 Nond N/A N/A Repaired-Tubes 7.(1)
P W defectIVejrepaired C41 None tubes andtinspectiall C;2 remaining.:. repaired tubes Plug..d. efective7epaired tubes in/this:S.Gi C-3 Perfo'rm' actioni for: C23 result of first:Tsample C-3 Inspect'sll): repaired. tubes The other None inLth.is S.G., plug S.G. jis:: C-1 defective tubes and inspect"20% of the repaired tubesiin the other S.G; Theiother Perform actionifor?C-2 S.G..;is'C-2 result of:first ; sample Notificationsto NRC pursuantato:50.72(b)(2)(1) of:101CFR~Part 50 TheJ.other Inspect -~all' repaired)lt'ubes S.G.~is.iC-3 in each S.G.-an'diplug defective'tubesV ~
- Notification.to NRC T pursuantito;50.72(b)(2)(1)
~
ofM 0;CFR Partis 0 " ~~~~ ~
(1)MEsshirepair[ method l:isiconsidsrsdlaTseparatsjipopulstlipsifoEditsisl& , ,f!scopeTexpaiG1on5:
PAGEll?0Fjl Proposed Amendment No. 138b l 09/05/96
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